Estimation of the uncertainty in TRAC/PF1-MOD1 predictions of production reactor plenum pressures

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7055879

Griggs, D P ^[1]

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1. Westinghouse Savannah River Co., Aiken, SC (United States)

The TRAC-PF1/MOD1 code (TRAC) is used to perform best-estimate analyses of certain postulated design-basis accidents (DBAs) in Savannah River Site (SRS) production reactors. One of the DBAs analyzed is an instantaneous double-ended guillotine break loss-of-coolant accident (LOCA). The TRAC analysis provides time-dependent plenum and tank bottom pressures for use as boundary conditions in a detailed analysis of a single fuel assembly. The quantification of uncertainty is an important element in determining safe operating power levels for SRS reactors. This motivates the estimation of the uncertainty in using spatial interpolations of the relatively coarse cell-average plenum pressure predictions obtained with TRAC to predict detailed reactor plenum pressure distributions. This result supports the adequacy of the {plus minus}5% plenum pressure uncertainty estimated for LOCA analyses.

• OSTI ID: 7055879
• Report Number(s): CONF-920606--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOUNDARY CONDITIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DESIGN BASIS ACCIDENTS
ENERGY TRANSFER
ERRORS
FAILURES
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
L REACTOR
LOSS OF COOLANT
MECHANICS
NATIONAL ORGANIZATIONS
OPERATION
PIPES
PRIMARY COOLANT CIRCUITS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
SAVANNAH RIVER PLANT
SIMULATION
SPECIAL PRODUCTION REACTORS
T CODES
TIME DEPENDENCE
US AEC
US DOE
US ERDA
US ORGANIZATIONS